Probabilistic assessment of excessive leakage through steam generator tubes degraded by secondary side corrosion

Cizelj, Leon; Hauer, I.; Guy, Rebecca; Cuvelliez, Ch.

doi:10.1016/s0029-5493(98)00229-5

Cited by 7 publications

(4 citation statements)

References 2 publications

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“…The assessment of the leakage was again based on an empirical relation between the defect size as measured by the non-destructive examination method and the experimentally determined leak rates at assumed fixed pressure differences (EPRI 1993). The failure function was formulated by (Cizelj, Hauer et al 1998) and (Cizelj and Roussel 2003):…”

Section: Odscc Under Tube Support Plates: Excessive Leakagementioning

confidence: 99%

“…The AVN#1 and AVN#2 estimators were proposed in (Cuvelliez and Roussel 1995) as alternatives to the proposal by EPRI (EPRI 1993). The properties of all three estimators are analyzed in detail in (Cizelj, Hauer et al 1998). For the purpose of this section, they are considered as empirical estimators of the 5% failure probability and are used to validate the probabilistic results.…”

Section: Leakage Through Odscc At Tube Support Platesmentioning

confidence: 99%

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Reliability of Degraded Steam Generator Tubes

Cizelj¹,

Guy²

2011

Steam Generator Systems: Operational Reliability and Efficiency

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Section: Odscc Under Tube Support Plates: Excessive Leakagementioning

confidence: 99%

Section: Leakage Through Odscc At Tube Support Platesmentioning

confidence: 99%

Reliability of Degraded Steam Generator Tubes

Cizelj¹,

Guy²

2011

Steam Generator Systems: Operational Reliability and Efficiency

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“…Cizelj 36 presented a logarithmic leak rate model. Given the defect size V i , the individual leak rate Q i is expressed as:…”

Section: Crack Opening Area and Fluid Leakagementioning

confidence: 99%

A probabilistic simulation of fluid leakage in multiple cracks situation

Xie

2002

Fatigue Fract Eng Mat Struct

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In pressure vessels and piping the leak‐before‐break (LBB) assessment method is employed to avoid any catastrophic failure prior to a detectable leakage. One of the most important parameter, the leak rate, is investigated in the present paper by means of the Monte Carlo method. A brief review is carried out with emphasis on aspects such as crack growth, crack size with detectable leakage, crack opening area and leak rate. Issues concerning the property and behaviour of multiple cracks are also covered along with a review of the characteristics of leak rate through distributed multiple cracks using a statistical simulation method. The simulation results show that the effect of multiple cracks is quite significant to the LBB concept. Both the relationship between leak rate and crack length (or time) and the statistical characteristics of the leak rate are considerably different for different initial crack conditions.

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“…Appropriate probabilistic method has already been proposed by the authors, 6 aiming at predicting the probability of excessive leaks in SG tubes, i.e. the probability that the sum of individual leak rates exceeds the allowable leak rate for given operating conditions and the distribution of defects in the steam generator.…”

Section: Introductionmentioning

confidence: 99%

Probabilistic evaluation of leak rates through multiple defects: the case of nuclear steam generators

Cizelj

Guy

2003

Fatigue Fract Eng Mat Struct

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A probabilistic approach aimed at predicting the probability of excessive leakage through flaws in tubes is proposed in the paper. The excessive leakage is assumed to occur when the sum of all individual leak rates through degraded tubes exceeds the predefined acceptable value. Additionally, a brief description of some estimators used in the field to obtain conservative estimates of the 95th percentile (e.g., upper limit) of the total leak rate is given. The conservatism of those estimators is quantified through failure probability in the two numerical examples. The leak rates through the individual flaws were evaluated using models developed by EPRI for assessment of outside diameter stress corrosion cracks (ODSCC) in tubes of steam generators in nuclear power plants assuming postulated hypothetical accidental conditions. The distributions of flaw sizes are based on inspection data obtained from Slovene and Belgian plants with 3/4 inch tubes made of Alloy 600 Mill Annealed. The numerical examples analyse the behaviour of the model for both small and large flaw sizes. The results include: prediction and discussion of the probability of excessive leakage; the conservatism of approximate estimators; comments on the sensitivity of the probability of excessive leakage to the major uncertainties inherent to data and models used. As a conclusion, some suggestions to improve both the efficiency of the numerical estimators and models used to estimate the leak rates through individual defects are given.

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Probabilistic assessment of excessive leakage through steam generator tubes degraded by secondary side corrosion

Cited by 7 publications

References 2 publications

Reliability of Degraded Steam Generator Tubes

Reliability of Degraded Steam Generator Tubes

A probabilistic simulation of fluid leakage in multiple cracks situation

Probabilistic evaluation of leak rates through multiple defects: the case of nuclear steam generators

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